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Technical Paper

A Nodal Kinetics and Thermohydraulics Analysis (NOKTA) Code for Analyzing Rod-Ejection Accidents and Other Transients in Nuclear Power Reactor Cores

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Pages 26-35 | Published online: 13 May 2017

References

  • H. FINNEMANN and A. GALATI, “NEACRP 3-D LWR Core Transient Benchmark Final Specifications,” NEACRP-L-335, Organization for Economic Cooperation and Development, Nuclear Energy Agency (1992).
  • H. FINNEMANN, H. BAUER, A. GALATI, and R. MAR-TINELLI, “Results of LWR Core Transient Benchmarks,” NEA/NSC/DOC (93) 25, Organization for Economic Cooperation and Development (1993).
  • C. L. WHEELER, C. W. STEWART, R. J. CENA, D. S. ROWE, and A. M. SUTEY, “COBRA-IV-I: An Interim Version of COBRA for Thermal-Hydraulic Analysis of Rod Bundle Nuclear Fuel Elements and Cores,” Pacific Northwest Laboratories (1976).
  • H. UEMATSU, S. IZUTSU, T. YAMAMOTO, R. YA-MASHITA, S. MUTO, and A. TOBA, “Development of a Three-Dimensional Transient Code for Reactivity-Initiated Events in Boiling Water Reactors-Models and Code Verifications,” Nucl. Technol., 88, 87 (1989).
  • H. P. CHOU, J. R. LU, and M. B. CHANG, “A Three-Dimensional Space-Time Model and Its Use in Pressurized Water Reactor Rod Ejection Analyses,” Nucl. Technol., 90, 142 (1989).
  • Y. TAKEUCHI, Y. TAKIGAWA, H. UEMATSU, S. EBATA, J. C. SHAUG, and B. S. SHIRALKAR, “TRACG TransientAnaly-sis Code-Three-Dimensional Kinetics Model Implementation and Applicability for Space-Dependent Analysis,” Nucl. Technol., 105, 162 (1993).
  • B. MONTAGNINI, P. RAFFAELLI, M. SUMINI, and D. M. ZARDINI, “A 3D Coarse-Mesh Time Dependent Code for Nuclear Reactor Kinetic Calculations,” Ann. Nucl. Energy, 23, 517 (1996).
  • S. LANGENBUCH, W. MAURER, and W. WERNER, “Coarse-Mesh Flux-Expansion Method for the Analysis of Space-Time Effects in Large Light Water Reactor Cores,” Nucl. Sci. Eng., 63, 437 (1977).
  • S. GLASSTONE and A. SESONSKE, Nuclear Reactor Engineering Reactor Design Basics, Chapman and Hall, New York (1994).
  • A. BEJAN, Heat Transfer, John Wiley & Sons (1993).
  • S. KAYA and S. ANGHAIE, “An Improved Numerical Method for Subchannel Cross-Flow Calculations,” Trans. Am. Nucl. Soc., 53, 263 (1986).
  • T. B. FOWLER, D. R. VONDY, and G. W. CUNNINGHAM, “Nuclear Reactor Core Analysis Code,” Oak Ridge National Laboratory (1969).

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